基于MCNP的多群计算特性,扩展了其多群功能,并与栅元均匀化程序WIMS耦合,实现了临界-燃耗耦合计算;采用WIMS产生的69群共振、自屏宏观中子截面,进行了栅元、组件计算以及实验对比,计算结果与其他方法的计算结果和实验结果一致,验证了此耦合程序的可靠性和正确性。最后,应用此耦合程序对西安脉冲堆第一循环的燃耗进行了计算和分析。

Based on the multigroup calculation feature of the MCNP code, the multigroup function is extended. The coupled code is used to calculate the burnup with the lattice homogenous code WIMS. The 69-group resonance and self-shield macroscopic neutron cross-section, is generated by the WIMS code to simulate the fuel cell and the fuel assembly and the comparative experiment is carried out. The calculation results are in good agreement with the results of other methods and experiments. It indicates that the coupled code is correct and rational. Finally, the paper uses the coupled code to compute and analyze the burnup of the Xi'an pulsed reactor.